The development of design technology on the safety parameter display system for the operability improvement of the nuclear power plant
Creators
- 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Description
The purpose of this study is, basically, threefold. Firstly, through detailed comparison, the difference between the safety parameters used in the EPG and CFMS is analyzed. Furthermore, to anticipate and extrapolate the problems that might be encountered when developing the CFMS system that utilizes safety parameters consistent with that of the EPG. Secondly, the setpoint analysis of the CFMS alarm algorithm was done for there is a possibility of causing spurious alarms since the alarm setpoint of the YGN 3,4 CFMS is not reflective of the plant operating conditions nor accident progression. Lastly, the analysis of the success path for each accident was done to help operator in mitigating the accident by using the pictorial path of the success path during an accident condition. Moreover, in this analysis, the contents of the concerns that KINS raised regarding the YGN 3,4 SPDS has been addressed from the designer's perspective. 33 figs., 16 refs. (Author) .new
Availability note (English)
MF available from INIS under the Report Number.Files
27063018.pdf
Files
(3.8 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 114 p.
- Report number
- KAERI/TR--519/94
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 27063018
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT REMOVAL; CONTAINMENT BUILDINGS; EMERGENCY PLANS; PRESSURE CONTROL; PWR TYPE REACTORS; REACTIVITY; REACTOR COOLING SYSTEMS; SAFETY ENGINEERING; SYSTEMS ANALYSIS
- Descriptors DEC
- BUILDINGS; CONTAINMENT; CONTROL; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; REMOVAL; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS